NL-02-072, Entergy Revision to Emergency Plan Implementing Procedures

Entergy Revision to Emergency Plan Implementing Procedures

ML021500603
Person / Time
Site:	Indian Point
Issue date:	05/24/2002
From:	Dacimo F Entergy Nuclear Northeast, Entergy Operations
To:	Document Control Desk, NRC/FSME
References
FOIA/PA-2003-0379, FOIA/PA-2003-0388, NL-02-072
Download: ML021500603 (63)

Text

SEntergy Entergy Nuclear Northeast Entergy Nuclear Operations, Inc.

Indian Point Energy Center 295 Broadway, Suite 1 PO. Box 249 Buchanan, NY 10511-0249 May 24, 2002 Re:

Indian Point Unit No. 1 and No. 2 Docket No.50-003 and No. 50-247 NL-02-072 U.S. Nuclear Regulatory Commission Attn: Document Control Desk Mail Station O-P1-17 Washington, DC 20555-0001

SUBJECT:

Revision to Emergency Plan Procedures

Dear Sir:

In accordance with 10 CFR 50.54(q) and 10 CFR 50.4(b)(5), Entergy Nuclear Operations, Inc., submits herewith a controlled copy of changes to the Emergency Plan procedures for Indian Point Units Nos. 1 and 2. These changes do not reduce the effectiveness of the Emergency Plan. The Emergency Plan, as a whole, continues to meet the standard of 50.47(b) and the requirements of Appendix E to 10 CFR 50.

There are no commitments contained in this letter. Should you or your staff have any questions, please contact Mr. Frank Inzirillo, Manager, Emergency Planning, (914) 271-7418.

Fred Dacimo Vice President - Operations Indian Point 2 Enclosure cc: Next page

NL-02-072 Page 2 of 2 Enclosure as noted:

cc:

Mr. Hubert J. Miller (enclosure - 2 copies)

Regional Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406-1498 Mr. Patrick D. Milano, Senior Project Manager, Section 1(without enclosure)

Project Directorate I Division of Licensing Project Management U.S. Nuclear Regulatory Commission Mail Stop O-8-C-2 Washington, DC 20555-0001 Senior Resident Inspector (enclosure)

U.S. Nuclear Regulatory Commission Indian Point Unit 2 P.O. Box 38 Buchanan, NY 10511

Emergency Planning Document Controlled Holder/Location:

FROM:

NRC Document Control Desk (Washington)

Document Holder Organization Emergency Planning Document Custodian

SUBJECT:

Emergency Planning Document Update Please update your controlled copy of the documents listed below as specified with the copy(s) attached. It is requested that the update be completed within 3 days of the effective date shown on the document cover page.

Please sign this memo indicating that you have completed the update as specified and return to:

Entergy Nuclear Indian Point Nuclear Generating Station Emergency Planning Department Buchanan Service Center Broadway & Bleakley Ayes.

Buchanan, NY 10511 Attn: Document Custodian Emergency Plan Implementing Procedures Table of Contents 4/29/02 4/11/02 Replace entire document IP-1008 Personnel Radiological Check and 7

6 Replace entire document Decontamination Manual Update, Readout and IP-1021 Printout of PROTEUS Plant 6

5 Replace entire document Parameter Data IP-1024 Emergency Classification 9

8 Replace entire document Obtaining Offsite Exposure Rates IP-1047 From MIDAS Using a Data 8

7 Replace entire document Terminal Update completed as specified:

Signature of Controlled Copy Holder TOC Copy # 14 TO:

Date

Emergency Plan Implementing Procedures Table of Contents IP-1001 Mobilization of Onsite Emergency Organization 13 5/25/01 IP-1002 Emergency Notification and Communication 25 9/6/01 IP-1003 Planned Discharge of Containment Atmosphere During Accident 7

4/16/01 Conditions IP-1004 Post Accident Offsite Environmental Surveys, Sampling and Counting 5

9/1/99 IP-1007 Dose Assessment 11 3/26/01 IP-1008 Personnel Radiological Check and Decontamination 7

4/29/02 IP-1009 Radiological Check and Decontamination of Vehicles 7

9/1/99 IP-1010 Central Control Room 4

3/6/02 IP-1011 Joint News Center 6

1/23/02 IP-1012 Onsite Medical Emergency 10 5/25/01 IP-1013 Protective Action Recommendations 8

11/1/99 IP-1014 Radiological Check of Equipment Before It Leaves the Site 6

9/1/99 IP-1015 Radiological Surveys Outside the Protected Area (Title Change) 9 3/26/01 IP-1016 Obtaining Meteorological Data 12 9/1/99 IP-1019 Coordination of Corporate Response 10 9/6/01 IP-1020 Airborne Activity Determination 8

01/12/01 IP-1021 Manual Update, Readout and Printout of Proteus Plant Parameter 6

4/29/02 Data IP-1022 Obtaining Meteorological, Radiological and Dose Assessment Data 5

9/1/99 from MIDAS IP-1023 Operations Support Center (OSC) 18 4/11/02 IP-1024 Emergency Classification 9

4/29/02 IP-1025 Cancelled 10/17/01 IP-1026 Emergency Data Acquisition 0

01/12/01 IP-1027 Personnel Accountability and Evacuation 16 4/11/02 IP-1030 Emergency Operations Facility (EOF) 5 9/6/01 As of 4/29/02 Page 1 of 2

Emergency Plan Implementing Procedures Table of Contents Modular Emergency Assessment & Notification System (MEANS) 0 3/26/01 As of 4/29/02 IP-1 033 IP-1035 Technical Support Center (TSC) 16 2/20/01 IP-1036 Estimation of Population dose Within the 10 Mile Emergency 6

9/1/99 Planning Zone IP-1037 Obtaining Offsite Reuter-Stokes Monitor Data 8

9/1/99 IP-1039 Offsite Contamination Checks 9

01/12/01 IP-1045 Activation of Alternate Emergency Operations Facility 9

5/18/01 IP-1047 Obtaining Offsite Exposure Rates From Midas Using a Data Terminal 8

4/29/02 IP-1048 Termination and Recovery 9

9/6/01 IP-1050 Security 3

4/11/02 Page 2 of 2

ENTERGY IP-1008 INDIAN POINT STATION Rev. 7 EMERGENCY PLANNING PERSONNEL RADIOLOGICAL CHECK AND DECONTAMINATION Prepared by:

Technical Reviewer:

Reviewer:

Reviewer:

Reviewer:

SNSC Review:

Approval:

Steve Hook

,_natr_

Print Name Signature Bryant Pergerson k

g Prnt Name ignature Print Name Slgnature Prnt Name Signature Print Name Signature Meeting Number Signature Secretary Frank Inzirillo cU.

6 Print Name Signaiure Effective Date:

ýd 7-9 Q z_

IP-1008 (Personnel Rad) R7.doc 20023181600 Date Date Date D~ate Uate D~ate SA

/0 4

Date

Personnel Radiological Check and Decon IP-1008 Rev. 7 PERSONNEL RADIOLOGICAL CHECK AND DECONTAMINATION 1.0 PURPOSE 1.1 To describe the methods Health Physics personnel use in the checking of personnel for contamination and their subsequent decontamination at the Buchanan Service Center.

2.0 DISCUSSION 2.1 Personnel who become contaminated while working in the Protected Area are checked out AND decontaminated at the plant facilities in the Unit No. 1 Nuclear Service Building.

2.2 ALL others are decontaminated at the Buchanan Service Center (see Addendum 8.1).

2.3 Decontamination of the individual shall be by normal washing in the shower using regular soap. IF normal washing WITH soap DOES NOT remove it, THEN decontamination shall proceed under medical supervision.

3.0 PRECAUTIONS AND LIMITATIONS NONE 4.0 EQUIPMENT AND MATERIALS 4.1 Clean coveralls are stocked at the Cortlandt Warehouse.

4.2 Decon materials are located at the Buchanan Service Center in the Emergency Operation Facility (EOF).

5.0 INSTRUCTIONS NOTE:

ALL PHONE NUMBERS AND FORMS SPECIFIED IN THIS PROCEDURE ARE IN APPENDICES A, B, C, AND D OF EMERGENCY TELEPHONE DIRECTORY (ETD).

Page 2 of 5

Personnel Radiological Check and Decon IP-1008 Rev. 7 NOTE:

IT SHOULD TAKE AT LEAST TWO MINUTES TO PROPERLY EXECUTE THE FRISK.

FOR LARGE NUMBERS OF INDIVIDUALS WHO HAVE TRAVELED TOGETHER AND ARE SUSPECTED TO BE CONTAMINATED, REPRESENTATIVE NUMBERS MAY BE CHECKED TO EXPEDITE THE EVACUATION.

DISCUSS THIS SITUATION WITH THE OFFSITE RADIOLOGICAL ASSESSMENT DIRECTOR (ORAD).

5.1 Perform, OR have the individual perform, the check for contamination using a E-140N OR RM-14 WITH an HP-210 probe. The instruments are available at the EOF. Ensure that personnel use the frisker properly.

5.2 IF the individual is NOT contaminated, LESS THAN 100 CPM above background, THEN record on FORM 7 AND report findings to the ORAD.

5.3 IF the individual is contaminated, GREATER THAN 100 CPM above background, THEN record on FORM 7 AND refer the individual to the shower room facility. Report findings to ORAD.

5.4 Segregate the contaminated individual to an area that has been set up as a contaminated area WITH signs AND Step Off Pads.

5.5 Initiate FORM 31a OR FORM 31b as APPROPRIATE.

Record initial contamination levels as recorded on FORM 7 BEFORE proceeding further.

5.6 Check EACH piece of clothing as it is removed AND segregate as to whether it is contaminated OR NOT contaminated.

Contaminated clothing should be placed in plastic bags which may be obtained from the storeroom stock.

Record on FORM 31a.

NOTE:

WHERE CLOTHING CONTAMINATION DOES NOT PLAY A PART, BUT BODY ORIFICES DO, FORM 31b SHOULD BE USED.

IN CERTAIN INSTANCES BOTH FORMS MIGHT BE REQUIRED.

5.7 Recheck individual AFTER clothing is removed.

Record on FORM 31a.

IF decontamination is required, THEN have the individual shower AND record as found data.

5.8 Recheck AFTER shower.

Repeat shower as necessary recording EACH recheck on FORM 31a.

Page 3 of 5

Personnel Radiological Check and Decon IP-1008 Rev. 7 5.9 Report results to the ORAD.

5.10 IF skin contamination occurs AND the normal washing WITH soap did NOT remove it, THEN decontamination shall proceed under the direction of medical supervision.

Materials AND supplies are kept in the Medical Office at the Buchanan Service Center. Record ALL decontamination steps AND surveys taken on FORM 31b.

5.11 Individuals should be whole body counted, AFTER decontamination is completed, WHEN there is a possibility that they have inhaled a quantity of radioactive material to exceed 200 DAC hours.

5.11.1 Reliable assay of thyroid burden AND calculation of intake should occur ONLY in the 12 hour1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> to 10 day interval post-intake.

5.11.2 Uncontaminated persons are unlikely to have a measurable intake.

5.11.3 Screening for significance of intake may be readily accomplish by MS-2/SPA-3 measurement of thyroid burden. See Reference 6.1.

5.11.4 Persons thought, by screening, to have intakes of 10% ALl should be whole body counted by arrangement.

5.11.5 All measurable S(ALI) above 10 DAC-hours OR N(ALI) above 50 DAC-hours equivalent for occupationally exposed persons shall be recorded in personnel records.

5.12 Turn in ALL completed forms to ORAD.

6.0 REFERENCES

6.1 IP-1005, "Use of MS-2/SPA-3 Tod Determine Thyroid Radioiodine Uptake".

7.0 ATTACHMENTS NONE 8.0 ADDENDUM 8.1 Buchanan Service Center Building.

Page 4 of 5

Personnel Radiological Check and Decon IP-1008 Rev. 7 ADDENDUM 8.1 Page 1 of 1 BUCHANAN SERIVICE CENTER BUILDING H

H H

AccountabiLty

OpFice, AssembLy Area Page 5 of 5

ENTERGY IP-1021 INDIAN POINT STATION Rev. 6 EMERGENCY PLANNING Manual Update, Readout and Printout of PROTEUS Plant Parameter Data Prepared by:

Technical Reviewer:

Reviewer:

Reviewer:

Reviewer:

SNSC Review:

Approval:

S. Hook Print Name B. Pergerson Print Name Print Name Print Name Print Name Meeting Number Frank Inzirillo Print Name Signature Signature Date Date Date Vate Date Date Uate Signature Effective Date:

H ý z qj..

IP-1021 (Proteus) R6 20023181100 Page 1 of 14

Proteus IP-1021 Rev. 6 Table of Contents Section Paqe 1.0 PURPOSE............................................................................................................................................

3 2.0 DISCUSSION.......................................................................................................................................

3 3.0 PRECAUTIONS AND LIMITATIONS................................................................................................

3 4.0 EQUIPMENT AND MATERIALS..................................................................................................

3 5.0 INSTRUCTIONS...................................................................................................................................

4 5.1 Manual Update of Plant Parameters in Proteus Computer................................................ 4 5.2 Initializing TSC Proteus Terminal.......................................................................................

6 5.3 Initializing EOF Proteus Terminal.......................................................................................

6 5.4 Display and Printout of Individual Groups..........................................................................

7 5.5 TSC Automatic Recurring Printout on Line Printer.............................................................

8 5.6 EOF Automatic Recurring Printout on Line Printer...................................

9 5.7 Enabling EOF Terminal for Computer Room...................................................................

11 5.8 Restoring TSC and Computer Room Proteus Line Printers...........................................

12 5.9 Restoring EOF Printer...........................................................................................................

12

6.0 REFERENCES

13 7.0 ATTACHMENTS :

Typical Proteus Keyboard Layout........................................................................

14 8.0 ADDENDUM None Page 2 of 14

Proteus IP-1021 Rev. 6 MANUAL UPDATE, READOUT AND PRINTOUT OF PROTEUS PLANT PARAMETER DATA 1.0 PURPOSE To describe the method of manual entry of plant parameter data into the Proteus computer terminal and the subsequent retrieval of data at the Emergency Operations Facility (EOF) and/or Technical Support Center (TSC) terminals.

2.0 DISCUSSION 2.1 There are six data points on the Plant Status Log (Groups 68 and 72) that are not continually monitored by the Proteus computer and hence are not available at the EOF or TSC. Therefore, it is necessary to manually input the data periodically (approximately 10 minute intervals).

2.2 The manual input may be accomplished using any Control Room or TSC Proteus terminal. The TSC member assigned to collect data will input this data.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 NONE 4.0 EQUIPMENT AND MATERIALS NONE Page 3 of 14

IP-1021 Rev. 6 Proteus 5.0 INSTRUCTIONS NOTE:

See Attachment 1 for typical keyboard layout.

5.1 Manual Update of Plant Parameters in Proteus Computer 5.1.1 Enable the display CRT by pressing the (yellow) C CRT CRT CRT Techni 1

2 3

Terminl TSC TSC TSC Control CRT 4 CRT 5 CRT 6 RT enable button

-al Support Center al Room Terminal ALM OPCON Control Room Terminal CRT CRT 5.1.2 Direct the cursor to the CRT selected above by pressing the (white) CRT button.

TSC TSC TSC Technical Support Center CRT 1 CRT 2 CRT 3 Terminal TSC TSC TSC Control Room CRT 4 CRT 5 CRT 6 Terminal ALM OPCON Control Room CRT CRT Terminal 5.1.3 Select your OPCON Access

a.

Select the Miscellaneous Function Menu by pressing the (blue) "MISC FUNCT" button.

Miscellaneous Function Menu Appears.

b.

Select the OPCON Access Screen by entering "1" (tan) and then press "EXECUTE".

OPCON ACCESS appears on screen.

c IF the present Level is GREATER THAN 3, THEN continue at Step 5.1.4.

d.

Contact the Reactor Operator.

e.

Identify yourself and your emergency function (TSC Data Processor).

f.

Ask for access code word that allows you to raise level to 4.

g.

Press "TAB FWD" as necessary to move the cursor to Access Code entry field.

h.

Enter the password in space for access code.

Page 4 of 14

Proteus IP-1021 Rev. 6

i.

Press "TAB FWD" to move the cursor to the next entry field.

j.

Enter "4" and then press "EXECUTE" Confirm that Present Level has changed to 4.

5.1.4 Select the Point Detail Screen by pressing "POINT DETAIL" (blue).

IF the purple entry screen does not appear press "CLEAR SCREEN".THEN perform the following:

a.

Repeat Steps 5.1.1 AND 5.1.2.

b.

Re-select the Point Detail Screen again.

5.1.5 Enter the computer address for the parameter data that you wish to enter:

PARAMETER UNITS GROUP ADDRESS VC Temp.

OF 68 KTO01 R-27 Vent Flow Rate CFM 72 KR027 R-27 Vent Monitor UCi/cc 72 KR028 Vent Flow Rate1 CFM 72 KF001 2

Main Stm. Exh.

LBS/HR 72 KF002 Air Ejector 3 CFM 72 KF003 Press "EXECUTE".

5.1.6 Enter value desired by pressing numerical keys.

Enter HHHHH for offscale high values.

Enter XXXXX for invalid values.

Press "EXECUTE".

Confirm that number entered appears in green on the screen.

5.1.7 To go to the next entry press "CLEAR SCREEN" AND repeat steps 5.1.1 AND 5.1.2.

5.1.8 REPEAT Steps 5.1.4 THROUGH 5.1.7 until all parameter data has been entered.

1This value (obtained from the Fan Building) is NOT required when R-27 flow rate (KR027) is available.

2This value is ONLY required if there is a radioactive release from the secondary side of a Steam Generator.

3This value is ONLY required if there is a radioactive release from the secondary side of a Steam Generator.

Page 5 of 14

Proteus IP-1021 Rev. 6 5.2 Initializing TSC Proteus Terminal 5.2.1 Energize terminal if necessary.

5.2.2 Select your OPCON Access

a.

Select the Miscellaneous Function Menu by pressing the (blue) "MISC FUNCT" button.

Miscellaneous Function Menu Appears.

b.

Select the OPCON Access Screen by entering "1" (tan) and then press "EXECUTE".

OPCON ACCESS appears on screen.

c Check Present Level.

IF GREATER THAN 3, THEN the terminal is initialized.

d.

IF OPCON Access level needs to be increased THEN contact the Reactor Operator.

e.

Identify yourself and your emergency function.

f.

Ask for access code word that shall allow you to raise level to 4.

g.

Press "TAB FW D" as necessary to move the cursor to Access Code entry field.

h.

Enter the password in space for access code.

i.

Press "TAB FWD" to move the cursor to the next entry field.

j.

Enter "4" and then press "EXECUTE" Confirm that Present Level has changed to 4.

5.3 Initializing EOF Proteus Terminal 5.3.1 Turn on power for CRT and Keyboard. Adjust monitor brightness as necessary.

5.3.2 Press the "SHIFT RIGHT" key AND the "CLEAR" key (red) at the same time.

5.3.3 Direct the TSC Data logger/SAS Proteus operator to enable the EOF terminal from the computer room (Refer to section 5.7).

5.3.4 Press the "CRT ENABLE" key (yellow).

Page 6 of 14

Proteus IP-1021 Rev. 6 5.4 Display and Printout of Individual Groups 5.4.1 Select the Trends Logs Groups Menu by pressing the (blue)

"TRENDS/LOGS/GROUPS" button.

Menu appears.

5.4.2 Press "TAB FWD" as necessary to move the cursor to the Function Number entry field.

5.4.3 Select the GROUP DISPLAY/ASSIGN/REVIEW option by entering "4" (tan) in the entry field and press "EXECUTE".

5.4.4 Select appropriate page/group for viewing/printing.

Group 66 Plant Status Form 42(a)T Group 67 Plant Status Form 42(a)C Group 68 Plant Status Form 42(a)B Group 70 Plant Status Form 42(c)T Group 71 Plant Status Form 42(c)C Group 72 Plant Status Form 42(c)B 5.4.5 Press "TAB FWD" as necessary to move the cursor to the Group entry field.

Enter the group number that you wish to display/print.

5.4.6 Press "TAB FWD" to move the cursor to the Action entry field.

Enter 1 to Display/Print 5.4.7 Press "TAB FWD" to move the cursor to the Device entry field.

Enter 1 to Display group on selected CRT.

Enter 2 to Print group on COMP ROOM printer Enter 3 to Print group on TSC printer.

Enter 8 to Print group on EOF printer.

Press "EXECUTE".

Group either appears on screen or on line printer.

5.4.8 To display another group press "PREV PAGE" OR "NEXT PAGE" as necessary.

Page 7 of 14

Proteus IP-1021 Rev. 6 5.4.9 To select another group for printout press "TAB FWD" as necessary to place the cursor in Group entry field.

Enter the group number that you wish to print.

Press "EXECUTE".

Note:

If the TSC line printer fails, the printout is automatically transferred to the computer room line printer. To restore printer refer to section 5.8.

5.5 TSC Automatic Recurring Printout on Line Printer 5.5.1 Select the Trends Logs Groups Menu by pressing the (blue)

"TRENDS/LOGS/GROUPS" button.

Menu appears.

5.5.2 Press "TAB FWD" as necessary to move the cursor to the option entry field.

5.5.3 Select the GROUP LOGS option by entering "6" (tan) in the entryfield and Press "EXECUTE".

5.5.4 Enable the Group Log as follows:

a.

Press "TAB FWD" as necessary to move the cursor to the LOG entry field.

b.

Enter the Group Log number into the entry field that you wish to Enable.

LOG "23" (tan)

LOG "24" (tan)

c.

Press "TAB FWD" to move the cursor to the Action entry field.

d.

Enter "4" (tan) to enable the Log AND press "EXECUTE".

5.5.5 Enter data collection and printout information as follows:

a.

Press "TAB FWD" as necessary to move the cursor to the Collection Action entry field.

b.

Enter "1" (tan) to entry field.

c.

Press "TAB FWD" to move the cursor to the Maximum Collection entry field.

d.

Enter "05" to select maximum number of collections before printout.

e.

Press "TAB FWD" to move the cursor to the hour entry field.

f.

Enter "0" in the hour entry field.

Page 8 of 14

Proteus IP-1021 Rev. 6

g.

Press "TAB FWD" to move the cursor to the minute entry field.

h.

Enter "01" in the minute entry field.

i.

Press "TAB FWD" to move the cursor to the seconds entry field.

j.

Enter "0" in the seconds entry field.

k.

Press "TAB FWD" to move the cursor to the Printout Action entry field.

I.

Enter "1" to the option field to enable printout.

m.

Press "TAB FWD" to move cursor to the next entry field.

n.

Enter "3" (tan) to the option field to enable printout.

Press "EXECUTE".

o.

IF CRT indicates "Execution of this form forbidden at current access level" THEN raise the OPCON Access level as per Step 5.2.2 and repeat Steps 5.5.1 to 5.5.5.

5.5.6 After data collection is finished, disable the data collection and printout as follows:

a.

Press "TAB FWD" as necessary to move the cursor to the Collection Action entry field.

b.

Enter "2" to the entry field to disable data collection.

c.

Press "TAB FWD" to move the cursor to the Printout Action entry field.

d.

Enter "2" (tan) to disable the Log printout.

e.

Press "EXECUTE".

Note:

If the EOF line printer fails, the printout is automatically transferred to the computer room line printer. To restore printer refer to section 5.9.

5.6 EOF Automatic Recurring Printout on Line Printer 5.6.1 Select the Trends Logs Groups Menu by pressing the (blue)

"TRENDS/LOGS/GROUPS" button.

Menu appears.

5.6.2 Press "TAB FWD" as necessaryto move the cursor to the Function Numberentry field.

5.6.3 Select the GROUP LOGS option by entering "6" (tan) in the entryfield and Press

""Execute".".

Press "NEXT PAGE".

Page 9 of 14

Proteus IP-1021 Rev. 6 5.6.4 Enable the Group Log as follows:

a.

Press "TAB FWD" as necessary to move the cursor to the LOG entry field.

b.

Enter the Group Log number into the entry field that you wish to Enable.

LOG "25" (tan)

LOG "26" (tan)

c.

Press "TAB FWD" to move the cursor to the Action entry field.

d.

Enter "4" (tan) to enable the Log AND press "EXECUTE".

5.6.5 Enter Data Collection and Printout information as follows:

a.

Press "TAB FWD" as necessary to move the cursor to the Collection Action entry field.

b.

Enter "1" (tan) to the Action entry field.

c.

Press "TAB FWD" to move the cursor to the Max Collection entry field.

d.

Enter "05" to select maximum number of collections before printout.

e.

Press "TAB FWD" to move the cursor to the hour entry field.

f.

Enter "0" in the hour entry field.

g.

Press "TAB FWD" to move the cursor to the minute entry field.

h.

Enter "01" in the minute entry field.

i.

Press "TAB FWD" to move the cursor to the seconds entry field.

j.

Enter "0" in the seconds entry field.

k.

Press "TAB FWD" as necessary to move the cursor to the Printout Action entry field.

I.

Enter "1" to the option field to enable printout.

m.

Press "TAB FWD" to move cursor to the next entry field.

n.

Enter "8" (tan) to the option field to enable printout.

Press "EXECUTE".

o.

IF CRT indicates "Execution of this form forbidden at current access level" THEN raise the access level as per Step 5.3.3 and repeat Steps 5.6.1 to 5.6.5.

Page 10 of 14

Proteus IP-1 021 Rev. 6 5.6.6 After data collection is finished, disable the data collection and printout as follows:

a.

Press "TAB FWD" as necessary to move the cursor to the Collection Action entry field.

b.

Enter "2" to the entry field to disable data collection.

c.

Press "TAB FWD" to move the cursor to the printout Action entry field.

d.

Enter "2" (tan) to disable the Log

e.

Press "EXECUTE".

5.7 Enabling EOF Terminal for Computer Room 5.7.1 Select your OPCON Access on the Computer Room Proteus terminal

a.

Select the Miscellaneous Function Menu by pressing the (blue) "MISC FUNCT" button.

Miscellaneous Function Menu Appears.

b.

Select the OPCON Access Screen by entering "1" (tan) and then press "EXECUTE".

OPCON ACCESS appears on screen.

c Check Present Level. IF the Level is set at 8, THEN continue at Step 5.7.2.

d.

Press "TAB FWD" as necessary to move the cursor to Access Code entry field.

e.

Enter the password 4 in space for access code.

f.

Press "TAB FWD" to move the cursor to the next entry field.

g.

Enter "8" and then press "EXECUTE" Confirm that Present Level has changed to 8.

5.7.2 Enable EOF terminal as follows:

a.

Press the "Batch" key. (Key is unmarked on function keypad at the top of the keyboard, the 6th key from the right on the third row).

b.

The screen output will display the following prompt:

THE PROTEUS BATCH SYSTEM

c.

Type the following:

IM,DO,KEYLOCK{7}=8

d.

Press the "SHIFT RIGHT" key and the "XMIT" key (red) at the same time.

4 Password is issued to the SAS - Proteus Operator by the IPCA Administrator.

Page 11 of 14

Proteus IP-1021 Rev. 6

e.

The screen output will display the following:

KEYLOCK (7)=8

f.

Exit the Batch Mode by typing XT

g.

Press the "SHIFT RIGHT" key and the "XMIT" key (red) at the same time.

5.8 Restoring TSC and Computer Room Proteus Line Printers 5.8.1 Identify cause of printer failure by opening printer and observing which red LED lights are lit and take actions as necessary to correct cause of failure.

5.8.2 Toggle the reset button to extinguish red LED lights.

5.8.3 Press the yellow button to reset the printer alarm.

5.8.4 Press the red & white button to place printer back on line.

5.8.5 At a Proteus Terminal select the Miscellaneous Function Menu by pressing the (blue) "MISC FUNCT" button.

Miscellaneous Function Menu Appears.

5.8.6 Select the Device RESTORE/FAIL/TRANSFER Screen by entering "2" (tan) and then press "EXECUTE".

OPCON ACCESS appears on screen 5.8.7 Press "PAGE FWD" as necessary to display page 4 of 5.

5.8.8 Enter Device Number that you wish to restore Device 46 COMP RM Printer Device 47 TSC Printer 5.8.9 Press "EXECUTE".

5.9 Restoring EOF Printer 5.8.1 At a Proteus Terminal select the Miscellaneous Function Menu by pressing the (blue) "MISC FUNCT" button.

Miscellaneous Function Menu Appears.

5.8.2 Select the Device RESTORE/FAIL/TRANSFER Screen by entering "2" (tan) and then press "EXECUTE".

OPCON ACCESS appears on screen 5.8.3 Press "PAGE FWD" as necessary to dispay page 4 of 5.

5.8.4 Enter Device Number 41 5.8.5 Press "EXECUTE".

Page 12 of 14

Proteus IP-1021 Rev. 6

6.0 REFERENCES

None 7.0 ATTACHMENTS, Typical Proteus Keyboard Layout 8.0 ADDENDUM None Page 13 of 14

IP-1 021 Rev. 6 Typical Proteus Keyboard Layout Sheet 1 of 1 Page 14 of 14 Proteus

ENTERGY INDIAN POINT STATION EMERGENCY PLANNING EMERGENCY CLASSIFICATION Prepared by:

Technical Review Reviewer:

Reviewer:

Reviewer:

SNSC Review:

Approval:

C. Kelly Walker 4c/,,-J

,4<2 Print Name Signature Date er:

~ 1 Print Name ig Print Name Siature Pnnt Name Print Name Meeting Number Frank Inzirillo Print Name Signature Signature Signature Secretary I

g ture Date

<9*-3 -sT Date Date Date Date Date Effective Date:

q-L (9

oz.

Biennial Review Reviewer/Date Reviewer/Date IP-1024 (Class) R9.doc Page 1 of 24 IP-1024 Rev. 9 D,

CONTROLLED COPY

Emergency Classification IP-1024 Rev. 9 EMERGENCY CLASSIFICATION 1.0 PURPOSE To describe the method for classification of emergencies as a Notification of Unusual Event (NUE), Alert, Site Area Emergency (SAE) or General Emergency (GE).

2.0 DISCUSSION 2.1 The symptom, event or barrier base classification may be made for NUE, Alert, Site Area or General Emergency, using Attachment 2.

2.2 IF a symptom, event or barrier base classification has been declared in a category followed by the same classification in another category THEN the classification continues to apply but an update should be made to offsite authorities in accordance with Reference 6.2.

2.3 IF a symptom, event or barrier based classification has been declared in a category followed by an increased classification THEN the higher classification shall be declared AND offsite authorities shall be notified in accordance with Reference 6.2.

2.4 Many of the classifications derived from the Reference 6.3 methodology are fission product barrier based. That is, a condition based upon loss or potential loss of one or more of the three fission product barriers. (Fuel cladding, RCS and Containment).

Refer to Attachment 1.

2.5 The following criteria serves as bases for event classification related to fission product barrier loss:

2.5.1 Unusual Event - any loss OR potential loss of containment.

2.5.2 Alert - Any loss OR potential loss of fuel clad or RCS.

2.5.3 Site Area Emergency - Any loss of both fuel clad AND RCS OR any potential loss of EITHER fuel clad OR RCS with a loss of any addition barrier.

2.5.4 General Emergency - Loss of any two barriers with loss OR potential loss of a third.

2.6 Event based classifications refer to occurrences with potential safety significance such as failure of Safety Injection pumps, safety valve failures, or electric power failures.

2.7 The symptom based classifications refer to those indicators that are measurable over a continuous spectrum, such as, core temperature, coolant levels and containment pressure.

2.8 The Technical Bases Document provides an explanation and rational for each of the Emergency Action Levels (EALs). This document is also used by individuals who are responsible for the implementation of this procedure as a technical reference and aid in EAL interpretation.

2.9 The EALs are grouped into nine categories to simplify their presentation and promote Page 2 of 24

Emergency Classification IP-1024 Rev. 9 a rapid understanding by their users. These categories are:

Category 1 CSFST Status Category 2 Reactor Fuel Category 3 Reactor Coolant System Category 4 Containment Category 5 Radioactivity Release/Area Radiation Category 6 Electrical Failures Category 7 Equipment Failures Category 8 Hazards Category 9 Other 2.10 Categories one through five are primarily symptom based.

The symptoms are indicative of actual or potential degradation of either fission product barriers or personnel safety.

2.11 Categories six, seven and eight are event based. Electrical Failures are those events associated with losses of either AC or vital DC electrical power. Equipment Failures are abnormal and emergency events associated with vital plant system failures, while hazards are those non-plant system related events which have affected or may affect plant safety.

2.12 Category nine provides the Emergency Director (Shift Manager) the latitude to classify and declare emergencies based on plant symptoms or events which in his judgment warrant classification. This judgment includes evaluation of loss or potential loss of one or more fission product barriers warranting emergency classification consistent with the barrier loss criteria as specified in section 2.5.

2.13 Categories are further divided into one or more subcategories depending on the types and number of plant conditions that dictate emergency classifications. For example, the Electrical Failures category has two subcategories whose values can be indicative of losses of electrical power sources. Loss of AC power sources and loss of DC power sources. An EAL may or may not exist for each subcategory at all four classification levels.

Similarly, more than one EAL may exist for a subcategory in a given emergency classification when appropriate (i.e. no EAL at the General Emergency level but three EALs at the Unusual Event Level).

2.14 The operating modes of operation are defined as follows:

2.14.1 Power Operations -When the reactor is critical and the neutron flux power range instrumentation indicates greater than2% of rated power.

2.14.2 Hot Shutdown -When the reactor is sub-critical by an amount greater than or equal to the margin as specified in Technical Specification 3.10 and Tavg is greater than 2007F and less than or equal to 5550F.

Page 3 of 24

Emergency Classification IP-1024 Rev. 9 2.14.3 Cold Shutdown -When the reactor is sub-critical by at least 1% Ak/k and Tv, is less than or equal to 2000F.

2.14.4 Refuel -Any operation involving movement of core components when vessel head is completely unbolted.

2.15.5 Defueled - Reactor vessel contains no irradiated fuel.

2.15 Plant Emergency Operating Procedures (EOPs) are designed to maintain or restore a set of critical safety functions that are prioritized for restoration efforts during accident conditions. By monitoring the critical safety functions status, the impact of multiple events can be inherently addressed.

2.16 The critical safety functions are monitored through the use of Critical Safety Function Status Trees (CSFSTs). When certain plant parameters exceed threshold values specified by the CSFST, the plant operator is directed to one or more functional restoration procedure in an attempt to restore those parameters to within acceptable limits. The following CSFSTs are utilized to be indicative of failures or potential failures of one or more fission product barriers:

2.16.1 Subcriticality - Orange or Red paths in this CSFST indicate losses of reactivity control which may pose a threat to fuel clad and RCS integrity.

2.16.2 Core Cooling - Orange OR Red paths in this CSFST indicate losses of core subcooling AND thus pose a direct threat to the integrity of the reactor fuel clad.

2.16.3 Heat Sink - The Red path of this CSFST is indicative of a loss of ability to remove decay heat from the core and thus poses a direct threat to fuel clad integrity.

2.16.4 Integrity - The Red path of this CSFST is indicative of a direct threat to RCS barrier integrity.

2.16.5 Containment - Red path of this CSFST is indicative to a loss of RCS barrier AND direct threat to the containment barrier integrity.

3.0 PRECAUTIONS AND LIMITATIONS NONE 4.0 EQUIPMENT AND MATERIALS NONE Page 4 of 24

Emergency Classification IP-1024 Rev. 9 5.0 INSTRUCTIONS 5.1 The Operator is alerted by initial event recognition or Control Room alarms.

5.2 The Operator shall notify the Shift Manager AND Watch Engineer.

5.3 The Operator may enter the Emergency Operating Procedures (EOPs) or Abnormal Operating Instructions (AOIs) while the Watch Engineer monitors the Critical Safety Function Status Trees (CSFST), if appropriate.

5.4 The Shift Manager shall evaluate Attachment 2 to determine IF a GE, SAE, ALERT or NUE classification applies THEN determine the highest classification and declare it, if applicable.

5.5 The Shift Manager shall assume the role of Emergency Director and initiate County, State AND NRC notifications in accordance with Reference 6.2.

5.6 The Emergency Director (Shift Manager) continues to evaluate future events and potential challenges from information supported by the Operator and Watch Engineer.

As conditions warrant, the Emergency Director (Shift Manager) shall re-enter Section 5.4.

5.7 If necessary the Emergency Director (Shift Manager) shall upgrade the emergency classification.

5.8 If no classification applies, the Shift Manager evaluates whether Technical Specifications Limits on LCO reportable under Reference 6.1 applies and performs the applicable notification as per Reference 6.1.

6.0 REFERENCES

6.1 SAO-124, Oral Reporting of Non-Emergency Items and Items of Interest and Significant Occurrence Reporting 6.2 IP-1002, Emergency Notification and Communication 6.3 NUMARC/NESP-007, Revision 2, Methodology for Development of Emergency Action Levels 7.0 ATTACHMENTS 7.1 Attachment I - Fission Product Barrier Loss & Potential Loss Indicators 7.2 - Emergency Action Levels 8.0 ADDENDUM None Page 5 of 24

Emergency Classification IP-1 024 Rev. 9 ATTACHMENT 1 Sheet I of 2 Fission Product Barrier Loss/Potential Loss Matrix (Those thresholds for which loss or potential loss is determined to be imminent, classify as though the threshold(s) has been exceeded)

Fuel Cladding RCS

"* RED path in F-0.2, CORE COOLING

"* Coolant activity >300 pCi/cc 1-131 equivalent

"* Core Exit Thermocouple Readings >1200OF Containment radiation monitor R-25 or R-26 >17R/hr Emergency Director Judgment Loss RCS subcooling < SI initiation setpoint due to RCS leakage Unisolated faulted (outside VC) ruptured steam generator

>0.17pCi/cc on R-42 OR >66 jaCi/cc on R-41 due to RCS leakage Emergency Director Judgment Page 6 of 24 Potential Loss ORANGE path in F-0.2, CORE COOLING RED path in F-0.3, HEAT SINK Core Exit Thermocouple Readings >7000 F RVLIS <39% w/no RCPs running Emergency Director Judgment Loss Potential Loss RED path on F-0.4, INTEGRITY RED path on F-0.3, HEAT SINK Primary system leakage exceeding capacity (>75GPM) of single charging pump Emergency Director Judgment

(

rgency Classification IP-1024 Rev. 9 ATTACHMENT I Sheet 2 of 2 Fission Product Barrier LosslPotential Loss Matrix (Those thresholds for which loss or potential loss is determined to be imminent, classify as though the threshold(s) has been exceeded)

Containment Potential Loss RED path F-0.5, CONTAINMENT Either:

Core exit thermocouples >1200°F OR Core exit thermocouples >700"F with RVLIS <39% w/no RCPs AND Restoration procedures not effective within 15 minutes

- Confirmed phase "B" isolation signal following confirmed LOCA with less than minimum containment cooling safeguards equipment operating Fan Cooler Units Oper.

Spray Pumps Req'd

<3 2

3 5

1 0

- Containment Pressure 47 psig and increasing

- >4% hyrdogen concentration in containment

- Containment radiation monitor R-25/26 reading >68 R/hr

- Emergency Director Judgment Loss Rapid uncontrolled decrease in containment pressure following initial increase due to RCS failure Either:

Any Phase "A" or Phase "B" or containment ventilation isolation valve(s) not closed when required following confirmed LOCA OR Inability to isolate any primary system discharging outside containment AND Radiological release to the environment exists as a result Both doors open on a VC airlock for >4 hrs.

OR Inability to close containment pressure relief or purge valves which results in a radiological release pathway to the environment for >4 hrs.

OR Any Phase A or Phase B or containment ventilation isolation valve(s) not closed when required which results in a radiological release pathway to the environment Unisolable release of secondary side to atmosphere from the affected steam generator(s) with primary to secondary leakage >Technical Specification limit in any steam generator Loss of primary coolant inside containment with containment pressure or sump level response not consistent with LOCA conditions Emergency Director Judgment Page 7 of 24 Emei

Emergency Classification IP-1024 Rev. 9 - Emergency Action Levels CATEGORY 1.0 CSFST STATUS Category General Site Area Alert Unusual Event 1.1

[SG2]

[SS2,SS4]

[SA2]

Subcriticality 1.1.3 {1,2}

1.1.2 (1,2}

1.1.1 (1,2}

RED path in F-0.1, Subcriticality RED path in F-0.1 Subcriticality Any Failure of an automatic AND AND trip signal to reduce power Actual or imminent entry into either:

Emergency boration is required range < 5%

RED Path in F-0.2, Core Cooling AND OR Manual trip is successful Red Path in F-0.3, Heat Sink 1.2

[fl,rl,cpl] [FCl,PC6,PC6]

[fpllfl,rl] [SS4,FC3,FC4]

Core Cooling 1.2.2 {1,2}

1.2.1 {1,2}

RED path in F-0.2,Core Cooling ORANGE or RED path in F-0.2, AND Core Cooling Functional restoration actions taken and procedures not effective within 15 minutes.

1.3

[fpl,rpl] [SS4,RCS1,FCI]

Heat Sink 1.3.1 {1,2}

RED path in F-0.3, HEAT SINK AND Heat sink is required 1.4

[rpl] [RCSl]

Integrity 1.4.1 {1,2}

RED Path on F-0.4, Integrity 1.5

[fl,rl,cpl] [PCI]

Containment 1.5.1 {1,2}

RED Path F-0.5, Containment resulting from loss I of coolant.

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Emergency Classification IP-1024 Rev. 9 - Emergency Action Levels CATEGORY 2.0 REACTOR FUEL Category General Site Area Alert Unusual Event

[fl.rplIrlj

[fl] [FC2]

[SU4]

2.1

[FC2,RCS1,RCS2,RCS4j 2.1.2 {1,2}

2.1.1 {1,2,3,4,5}

Coolant Activity 2.1.3 {1,2}

Coolant Activity > 300 jiCilcc 1-131 Coolant sample Coolant activity > 300 !iCi/cc 1-131 equivalent activity:

equivalent and any of the following:

> 601(E bar) liCi/cc

• RED path on F-0.4, Integrity

• Primary system leakage exceeding capacity (> 75 gpm) of single charging pump

• RCS subcooling < SI initiation setpoint due to RCS leakage

• Rise in R-41 offscale or R-42

>0.17 [LCi/cc due to RCS leakage 2.2

[fl,rl,cpl] [PC5]

[fl,rl] [FC5]

[rI] [RCS4]

Containment 2.2.3 {1,2}

2.2.2 {1,2}

2.2.1 {1,2}

Radiation Containment Radiation Containment Radiation monitor R-25 Rise in R-41 offscale or R-42 monitor R-25 or R-26 or R-26 > 17 R/HR

> 0.1 7gCi/cc due to RCS leakage

> 68 RJHR

[AA2]

[AU2]

2.3 2.3.2 {1,2,3,4,5}

2.3.1 (1,2,3,4,5}

Refueling Confirmed sustained alarm on ANY of Spent fuel pool Accidents or the following radiation monitors resulting (reactor cavity during Other Radiation from fuel damage caused by an refueling ) water level Monitors uncontrolled fuel handling process:

cannot be restored

"* R-2/R-7 Vapor Containment Area and maintained above Monitors Technical

"* R-5 Fuel Storage Building Area Specification Monitor minimum water level

"* R-25 or 26 Vapor Containment High Radiation Area Monitors

[AA2]

2.3.3 {1,2,3,4,5}

Report of visual observation of irradiated fuel uncovered

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Emergenr' Classification IP-1024 Rev. 9 - Emergency Action Levels URA I L-UKY 3.U RIEACTOR COOLANT SYSTEM Category General Site Area Alert Unusual Event

[fpl,rl][SS5, SS4,FC4]

[rpl] [RCS2]

[SU5]

3.1 3.1.3 {1,2,3,4}

3.1.2 {1,2}

3.1.1 {1,2}

RCS Leakage RVLIS cannot be maintained Primary system leakage Unidentified or pressure

> 39% with no RCP's running exceeding capacity (> 75 boundary leakage OR gpm) of single charging

> 10 gpm With the reactor vessel head removed, pump OR it is reported that water level in the Identified leakage reactor vessel is dropping in an

> 25 gpm uncontrolled manner and core uncovery is likely 3.2

[rpl,cl] [PC4,RCS2]

[cl] [PC4]

3.2.2 {1,2}

3.2.1 {1,2} Unisolable Primary to Secondary Leakage Unisolable release of secondary side to release of secondary side atmosphere from the affected steam to atmosphere from the generator(s) with primary to secondary affected steam leakage exceeding capacity (> 75 generator(s) with primary gpm) of a single charging pump to secondary leakage >

[fl,cl] [PC4,FC2]

Technical Specification 3.2.3 {1,2}

limit in any Steam Unisolable release of secondary side to Generator atmosphere from the affected steam generator(s) with primary to secondary leakage > Technical Specification limit in any steam generator AND Coolant activity > 300 ltCilcc of 1-131 equivalent 3.3

[rl] [RCS2]

RCS Subcooling 3.3.1 {1,2}

RCS subcooling <SI initiation setpoint due to RCS leakage

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Emergency Classification IP-1024 Rev. 9 - Emergency Action Levels CATEGORY 4.0 CONTAINMENT Category General Site Area Alert Unusual Event

[fl,ri,cpl] [PC2,FC2,FC5]

[rl,cl] [PC2]

[cl] [PC7]

414.1.4

{1,2}

4.1.2 {1,2}

4.1.1 {1,2}

Confirmed Phase "B" isolation signal following Rapid uncontrolled decrease in Both doors open on a VC airlock Containment confirmed LOCA with less than minimum containment containment pressure following for > 4 hrs.

Integrity Status cooling safeguards equipment operating, Table 4.3 initial increase due to RCS failure OR AND OR Inability to close containment Any indicators of fuel clad loss, Table 4.1 Loss of primary coolant inside pressure relief or purge valves containment with containment which results in a radiological

[fplI/fI,rl,cl] [PC2,FCI,FC2,FC3,FC4,FC5]

pressure or sump level response release pathway to the 4.1.5 {1,2}

not consistent with LOCA environment for > 4 hrs.

EITHER:

conditions OR Rapid uncontrolled decrease in containment Any Phase "A" or Phase "B" or pressure following initial increase due to RCS containment ventilation isolation failure valve(s) not closed when required OR which results in a radiological Loss of primary coolant inside containment with release pathway to the containment pressure or sump level response not environment consistent with LOCA conditions AND Any indications of fuel clad damage, Table 4.2

[fpl/fI,rI,cl] [PC3,FCI,FC2,FC3,FC4,FC5]

[rl,cl] [PC3]

4.1.6 {1,2}

4.1.3 {1,2}

EITHER:

EITHER:

Any Phase "A" or Phase "B" or CVI valve(s) not Any Phase "A" or Phase "B" closed when required following confirmed LOCA or CVI valve(s) not closed when OR required following confirmed Inability to isolate any primary system discharging LOCA outside containment OR AND Inability to isolate any primary Radiological release to the environment exists as a system discharging outside result containment AND AND Any indicators of fuel clad damage, Table 4.2 Radiological release to the environment exists as a result

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\\

Emergency Classification IP-1024 Rev. 9 - Emergency Action Levels CATEGORY 4.0 CONTAINMENT Category General Site Area Alert Unusual Event

[fpllfl,rl,cl] [RCS3,FCI,FC2,FC3,FC4,FC5]

[rl,cl] [RCS3]

4.2 4.2.2 {1,2}

4.2.1 {1,2}

Unisolable faulted (outside VC) ruptured steam Unisolable faulted (outside VC)

SG Tube Rupture generator ruptured steam generator w/Secondary AND Release Any indicators of fuel clad damage, Table 4.2

[fl,rl,cpl] [PC2]

4.3 4.3.1 {1,2}

4% Hydrogen concentration in containment Combustible Gas Concentrations

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Emergency Classification - Emergency Action Levels CATEGORY 4.0 CONTAINMENT Table 4.1 Fuel Clad Loss Indicators

1. Coolant activity > 300 liCi/cc of 1-131 equivalent

2.

Containment radiation monitor R-25/R-26 reading > 17 R/hr

3.

RED path in F-0.2, CORE COOLING Table 4.2 Fuel Clad Damage Indicators

1. ORANGE or RED path in F-0.2, CORE COOLING

2.

RED path in F-0.3, HEAT SINK AND Heat sink is required

3.

Coolant activity > 300 [jCI/cc of 1-131 equivalent

4.

Containment radiation monitor R-25/R-26 reading > 17 R/hr Table 4.3 Minimum Containment Cooling Safeguards Equipment Fan Cooler Units Operating Spray Pumps Required

<3 2

3 1

5 0

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Emergency Classification IP-1024 Rev. 9 - Emergency Action Levels CATEGORY 5.0 RADIOACTIVITY RELEASE Category General Site Area Alert Unusual Event

[AG1]

[AS1]

[AA1]

[AU1]

5.1 Effluent Monitors 5.1.4 {1,2,3,4,5}

5.1.3 {1,2,3,4,5}

5.1.2{1,2,3,4,5}

5.1.1{1,2,3,4,5}

A valid reading on any A valid reading on any A valid reading on any A valid reading on any monitors Table 5.1 column monitors Table 5.1 column monitors Table 5.1 monitors Table 5.1 column "GE" for > 15 minutes "SAE" for > 15 minutes column "Alert for "NUE" for unless dose assessment can unless dose assessment can

> 15 minutes unless

> 60 minutes unless confirm releases are below confirm releases are below dose assessment can sample analysis can Table 5.2 column "GE" within Table 5.2 column "SAE" within confirm releases are confirm release rates this time period, this time period, below Table 5.2 column

< 2 x technical "Alert" within this time specifications within this

period, time period.

[AG1]

[AS1]

[AAI]

[AU1]

5.2 Dose Projections/

5.2.5 {1,2,3,4,5}

5.2.4 {1,2,3,4,5}

5.2.2{1,2,3,4,5}

5.2.1{1,2,3,4,5}

Environmental Measurements/

Dose projections or field Dose projections or field Confirmed sample Confirmed sample analysis Release Rates surveys resulting from an surveys resulting from an analysis for gaseous or for gaseous or liquid actual imminent release actual imminent release which liquid release rates release rates which indicate doses/dose indicate doses/dose rates >

> 200 x technical

> 2 x technical rates > Table 5.2 column Table 5.2 column "SAE" at the specifications limits for specifications limits for "GE" at the site boundary or site boundary or beyond.

> 15 minutes

> 60 minutes.

beyond.

[AA1]

5.2.3{1,2,3,4,5}

Dose projections or field surveys resulting from an actual imminent which indicate doses/dose rates > Table 5.2 column "Alert" at the site boundary or beyond.

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(

Emergency Classification IP-1024 Rev Q - Emergency Action Levels CATF(GORY £ fi RAfI31AA.TIVITV RPl PA*:

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 15 of 24 Category General Site Area Alert Unusual Event 5.3 Area Radiation Levels

[AA3]

[AU2]

5.3.2{1,2,3,4,5}

5.3.1 {1,2,3,4,5}

Sustained area radiation Any sustained direct ARM levels > 15 mRem/hr in readings > 100 x alarm or EITHER:

offscale high resulting from Control Room an uncontrolled process OR Central Alarm Station and Secondary Alarm Station

[AA3]

5.3.3{1,2,3,4,5}

Sustained abnormal area radiation levels > 8 R/hr within any areas, Table 5.3 AND Access is required for safe operation or shutdown

Emergency Classification - Emergency Action Levels CATEGORY 5.0 RADIOACTIVITY RELEASE Monitor GE SAE Alert UE R-27 53 giCi/cc 5.3 jiCi/cc 5.3 E-1 [tCi/cc 2.3 E-3 jiCi/cc R-44 53 igCi/cc 5.3 jiCi/cc 5.3 E-1 jiCi/cc 2.3 E-3 giCi/cc R-54 N/A N/A 2.5 E-1 RiCi/cc 2.5 E-3 RCi/cc R-49 N/A N/A 2.7 E-2 RiCi/cc 2.7 E-4 pCi/cc Table 5.2 Dose Projection/Env. Measurement Classification Thresholds GE SAE Alert TEDE 1000 mRem 100 mRem 10 mRem CDE Thyroid 5000 mRem 500 mRem N/A External Exposure Rate 1000 mRem/hr 100 mRem/hr 10 mRem/hr Thyroid exposure rate 5000 mRem/hr 500 mRem/hr N/A (for 1 hr. of inhalation)

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 16 of 24 Table 5.1 Effluent Monitor Classification Thresholds IP-1 024 Rev. 9

Emergency Classification - Emergency Action Levels CATEGORY 5.0 RADIOACTIVITY RELEASE

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 17 of 24 IP-1024 Rev. 9 Table 5.3 Plant Areas

"* Condensate Storage Tank

"* RWST

"* Service Water Pump Structure

"* Service Water Valve Pit East

"* Fuel Storage Building

"* Primary Auxiliary Building/Fan House

"* 480 Volt Switchgear Room (Control Building)

"* Cable Spreading Room/Electrical Tunnel

"* Diesel Generator Building/Fuel Tank Area

"* Auxiliary Feedwater Pump Building

"* Battery Room (Control Building 33'0" ele.)

Emergency Classification IP-1024 Rev. 9 - Emergency Action Levels CATEGORY 6.0 ELECTRICAL FAIL IIRI=R Category General Site Area Alert Unusual Event

[SG1]

[SS1]

[SA1]

[SU1]

6.1 6.1.5 {1,2}

6.1.4 {1,2) 6.1.2 (3,4,5) 6.1.1 {1,2,3,4,5}

Loss of AC Power Loss of all emergency AC Loss of AC power to all 480 volt Loss of AC power to all 480 volt busses (5A, Unplanned loss of offsite Sources power busses (5A,2A/3A,6A) for 2A/3A, 6A) for > 15 minutes.

power to all 480V AND EITHER:

> 15 minutes.

AND busses(5A,2A/3A,6A) for >

Power restoration to AND Inability to power required core cooling/

15 minutes.

required core cooling Inability to power required core spent fuel cooling systems with alternate systems is not likely in cooling systems with alternate power sources for > 15 minutes.

1 hr.

power sources for > 15 minutes.

[SA5]

OR 6.1.3 (1,2)

Actual or imminent entry AC power capability to 480 volt busses into ORANGE or RED (5A,2A/3A,6A) reduced to only one of the path on F-0.2, "Core following sources for > 15 minutes.:

Cooling" 480V EDG 21 480V EDG 22 480V EDG 23 Unit Auxiliary Transformer*

Station Auxiliary Transformer*

13.8 KV gas turbine auto transformer*

with 86P or 86BU tripped, all offsite power supplies must be considered as one power supply

[SS3]

[SU7]

6.2 6.2.2 (1,2) 6.2.1 (3,4)

Loss of DC Power Loss of bus voltage (< 105 vdc) for Unplanned loss of bus Sources

> 15 minutes on all of the DC voltage (< 105 vdc) for Busses.

> 15 minutes on any DC bus resulting in the loss of decay heat removal capability.

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 18 of 24

Emergency Classification

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 19 of 24 IP-1024 Rev. 9 - Emergency Action Levels CATEGORY 7.0 EQUIPMENT FAILURES Category General Site Area Alert Unusual Event

[SU2]

7.1 7.1.1 {1,2}

Technical Specifications/

Plant is not brought to required Requirements operating mode within Technical Specifications LCO Action Statement Time.

[HS2]

[HA1]

[HUl]

7.2 7.2.5 {1,2,3,4,5}

7.2.2 {1,2}

7.2.1 {1,2}

System Failures or Control Control Room Evacuation Turbine failure generated missiles Report of main turbine failure requiring Room Evacuation AND which causes or potentially causes turbine trip resulting in:

Plant control cannot be any required safety related system or Damage to turbine generator seals established per A0127.1.9, structure to become inoperable, causing release of lubricating oil or "Control Room hydrogen Inaccessibility/ Safe

[HA5]

OR Shutdown" in 15 minutes 7.2.3 {1,2,3,4,5}

Casing penetration Entry into AOI-27.1.9, "Control Room Inaccessibility/ Safe Shutdown Control"

[SA3]

7.2.4 {3,4}

Reactor coolant temperature cannot be maintained < 200°F

Emergency Classification

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[SS6]

[SA4]

[SU3]

7.3 Loss of Indications/

7.3.4 {1,2}

7.3.3 {1,2}

7.3.1 {1,2}

Alarms/Communication Loss of most (approx. 75%)

Unplanned loss of most (approx.

Unplanned loss of most (approx. 75%)

Capability safety system annunciators 75%) safety system annunciators or safety system annunciators or or indications on Control indications on Control Room Panels indications on Control Room Panels Room Panels for > 15 minutes for > 15 minutes AND AND AND Loss of ability to monitor Increased surveillance is required for Increased surveillance is required for critical safety function status safe plant operation safe plant operation AND EITHER:

[SU6]

AND A significant plant transient in 7.3.2 {1,2,3,4,5}

A significant plant transient in progress Loss of all communications capability progress OR affecting the ability to EITHER:

Proteus and SAS are unavailable Perform routine operations OR Notify offsite agencies or personnel

Emergency Classification IP-1024 Rev. 9 - Emergency Action Levels CATEGORY 8.0 HAZARDS Category General Site Area Alert Unusual Event

[HGI]

[HSI]

[HA4]

[HU4]

8.1 8.1.4 {1,2,3,4,5}

8.1.3 {1,2,3,4,5}

8.1.2 {1,2,3,4,5}

8.1.1 {1,2,3,4,5}

Security Security Event which Intrusion into a plant Intrusion into plant Protected Area by Bomb Device or other indication of attempted Threats results in:

security vital area an adversary sabotage discovered within plant Protected Area Loss of plant control by an adversary OR but outside Plant Vital Areas, Table 8.2 from the Control OR Any security event which represents OR Room Any security event an actual substantial degradation of Any security event which represents a potential AND which represents the level of safety of the plant, degradation in the level of safety of the plant Loss of remote actual or likely shutdown capability failures of plant systems needed to protect the public.

[HA2]

[HU2]

8.2 8.2.3 {1,2,3,4,5}

8.2.1 {1,2,3,4,5} Confirmed fire in or contiguous to Fire or Fire or explosion in any plant area, any plant area, Table 8.2 not extinguished in Explosion Table 8.2, which causes or potentially 15 minutes of Control Room notification.

causes any required safety related

[HU1]

system or structure to become 8.2.2 (1,2,3,4,5} Report by plant personnel of an inoperable explosion within Protected Area boundary which impacts plant safety related systems or structures.

[HAI]

[HU1]

8.3 8.3.3 (1,2,3,4,5}

8.3.1 {1,2,3,4,5}

Man-Made Vehicle crash or projectile impact Vehicle crash into or projectile which impacts plant Events which causes or potentially causes safety related structures or systems within any required safety related system or Protected Area boundary structure to become inoperable,

[HU3]

Table 8.2 8.3.2 (1,2,3,4,5}

[HA3]

Report or detection of toxic or flammable gases 8.3.4 {1,2,3,4,5}

that could enter or have entered within the Report or detection of toxic or Protected Area boundary in amounts that could flammable gases within a plant area, affect the health of plant personnel or safe plant Table 8.2, in concentrations that will operation be life threatening to plant personnel OR or preclude access to equipment Report by local, county or state officials, or Unit 3, (even when using personal protective for potential evacuation of site personnel based on equipment) needed for safe plant offsite event operation

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 21 of 24

Emergency Classification IP-1024 Rev. 9 Category 8.4 Natural Events r

1 General Site Area - Emergency Action Levels CATEGORY R-0 HAZARDSR Alert

[HA1]

8.4.4 {1,2,3,4,5}

Earthquake felt in-plant based upon consensus of Control Room Operators on duty AND Notification from Unit 3 that an earthquake of a magnitude > 0.15g horizontal or > 0.10g vertical has occurred.

[HAI]

8.4.5 {1.2.3.4.5} Sustained winds

> 100 mph OR Tornado strikes a plant vital area, Table 8.2

[HA1]

8.4.6 (1,2,3,4,5) Assessment by the Control Room personnel that a natural event has occurred which causes or potentially causes any required safety system or structure to become inoperable, Table 8.2

[HAl]

8.4.7 {1,2,3,4,5}

River level 15' (OSML)

OR Low service water bay level resulting in a loss of service water flow

+/- ___________________________

I 1 ________________________________________

.1 Unusual Event

[HUll 8.4.1 (1,2,3,4,5) Earthquake felt in plant based upon a consensus of Control Room Operators on duty AND Notification received from Unit 3 that an earthquake has been detected on their instrumentation.

[HUl]

8.4.2 (1,2,3,4,5)

Report by plant personnel of tornado within plant Protected Area boundary

[HUI]

8.4.3 (1,2,3,4,51 River level Ž 14.5' (OMSL)

OR Service water bay level < -4.5' (OMSL)

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 22 of 24

Emergency Classification - Emergency Action Levels CATEGORY 8.0 HAZARDS

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 23 of 24 IP-1024 Rev. 9 Table 8.2 Plant Vital Areas Condensate Storage Tank RWST Service Water Pump Structure Service Water Valve Pit East Fuel Storage Building Primary Auxiliary Building/Fan House Vapor containment Building 480 Volt Switchgear Room (Control Building)

Cable Spreading Room/Electrical Tunnel Central Control Room Diesel Generator Building/Fuel Tank Area Auxiliary Feedwater Pump Building Battery Room (Control Building 33'0" ele)

Central Alarm Station

Emergency Classification IP-1024 Rev. 9 - Emergency Action Levels CATEGORY 9.0 Category General Site Area Alert Unusual Event 9.1

[HG2]

[HS3]

[HA6]

[HU5]

Other 9.1.7 {1,2,3,4,5}

9.1.5 {1,2,3,4,5) 9.1.3 {1,2,3,4,5}

9.1.1 {1,2,3,4,5}

As determined by the Shift As determined by the Shift Manager or Any event, as determined by Any event, as determined Manager or Emergency Director, Emergency Director, events are in progress the Shift Manager or by the Shift Manager or events are in progress which which indicate actual or likely failures of Emergency Director, that Emergency Director, that indicate actual, or imminent core plant systems needed to protect the public, could cause or has caused could lead to or has led to a damage and the potential for a Any releases are not expected to result in actual substantial potential degradation of the large release of radioactive exposures which exceed EPA PAGs.

degradation of the level of level of safety of the plant.

material in excess of EPA PAGs safety of the plant.

outside the site boundary.

[FC7,RCS6,PC8]

[FC7,RCS6,PC8]

9.1.6 {1,2}

[FC7,RCS6]

[PC8]

9.1.8 {1,2}

Any event, as determined by the Shift 9.1.4 {1,2) 9.1.2 {1,2}

Any event, as determined by the Manager or Emergency Director, that could Any event, as determined by Any event, as determined Shift Manager or Emergency lead or has led to EITHER:

the Shift Manager or by the Shift Manager or Director, that could lead or has led Loss or potential loss of both fuel clad Emergency Director, that Emergency Director, that to a loss of any two fission product and RCS barrier, Attachment A.

could lead or has led to a could lead to or has led to a barriers and loss or potential loss of OR loss or potential loss of either loss or potential loss of the third, Attachment 1.

Loss or potential loss of either fuel clad fuel clad or RCS barrier, containment, Attachment 1.

or RCS barrier in conjunction with a loss.

of containment, Attachment 1.

[1]= Power Operations [2]= Hot Shutdown [3]= Cold Shutdown [4]= Refuel [5]= Defuel Page 24 of 24

ENTERGY INDIAN POINT STATION EMERGENCY PLANNING OBTAINING OFFSITE EXPOSURE RATES FROM MIDAS USING A DATA TERMINAL Prepared by:

Technical Reviewer:

Reviewer:

Reviewer:

Reviewer:

SNSC Review:

Approval:

Steve Hook Print Name Bryant Pergerson Print Name Signature IfI e

Print Name Print Name Print Name Meeting Number Frank Inzirillo Print Name 6ignaiure signature Signature becretary

-fo alute O A-Date Date Date Date Date "Date ate CONTROLLED COPY Continuous Use Effective Date: -

Lý I Z10-L IP-1047 (MIDAS Exp) R2.doc 20023181600 Page 1 of 15 I P-1 047 Rev. 8

ENTERGY IP-1047 INDIAN POINT STATION Rev. 8 EMERGENCY PLANNING OBTAINING OFFSITE EXPOSURE RATES FROM MIDAS USING A DATA TERMINAL 1.0 PURPOSE 1.1 Provide a method for obtaining offsite airborne radioactive release exposure rates from the Meteorological Information and Dose Assessment System (MIDAS) using the Control Room hard copy terminal or via modem with any Windows 95/98 computer terminal.

2.0 DISCUSSION 2.1 The manual and computerized (Modular Emergency Assessment and Notification System) methods for calculating offsite exposure rates, Reference 6.1, determines the Total Effective Dose Equivalent (TEDE) exposure rates for noble gases (Form 6b) and the Thyroid Total Organ Dose Equivalent (TODE) exposure rates for noble gasses and iodines (Form 6c). Exposure rates are calculated forthe site boundary, 2 mile, 5 mile, and 10 mile radius.

2.2 The MIDAS computer can be used as an additional method of performing dose assessment calculations. The MIDAS computer ZCRISA task determines the TEDE exposure rates for noble gases and TODE exposure rates for noble gasses and iodines at the site boundary, 2 mile, 5 mile and 10 mile radius. The projected whole body and thyroid dose can also be calculated by entering an expected duration of the radioactive release.

3.0 PRECAUTIONS AND LIMITATIONS 3.1 The default for the iodine to noble gas ration (I/NG) is 1/10,000 for all releases except a main steam line release with the value 1/100.

4.0 EQUIPMENT AND MATERIALS 4.1 Texas Instruments, Silent 700/1200 BPS or Travel Mate 1200, data terminal.

4.2 Windows 95/98 computer terminal with modem.

5.0 INSTRUCTIONS NOTE:

ALL PHONE NUMBERS AND FORMS SPECIFIED IN THIS PROCEDURE ARE LOCATED IN APPENDICES A, B, C, AND D OF EMERGENCY TELEPHONE DIRECTORY (ETD).

Page 2 of 15

ENTERGY IP-1047 INDIAN POINT STATION Rev. 8 EMERGENCY PLANNING 5.1 Obtaining offsite exposure rates using hard copy terminal 5.1.1 Toggle the "UPPER CASE" switch "dot" side up. Toggle the "ON LINE" switch "dot" side down. Toggle the "LOCAL COPY" switch "dot" side up.

5.1.2 Place terminal power switch in "ON" position (located at back right corner of the terminal).

a.

Ensure the green "PRINT" light is on, IF NOT depress the "PRINT" key.

5.1.3 Check the terminal's configuration. Push the "CMD" THEN type "C" AND press "RTN". The first of six or seven lines of options is displayed. Options correspond to the characters in parenthesis. Verify that the last character in each line represents the correct option. Change the option by typing the character key below that option.

a.

Configuration Correct Options Speed - High (1200 Baud), Low (300 Baud):

(H/L)

H Parity - Even, Odd, Space, or Mark:

(E/O/S/M)

S Print control characters:

(Y/N)

N Xon/Xoff enabled:

(Y/N)

Y Aural monitor enabled:

(Y/N)

Y Printer off at power up:

(YN)

Y Answer on Nth ring - N = :

(0-9) 1 5.1.4 Push the "CMD" key, THEN push the "D" key.

5.1.5 The system will ask for the dial number. Dial MIDAS by typing in the number listed in EPD Book 2, Appendix C. Preface (914) area code numbers with (9). Preface (212) area code numbers with (91). Push the "RTN" key.

5.1.6 AFTER the system dials MIDAS, ringing is heard AND the "LINE RDY" light will blink.

5.1.7 The connection is made WHEN a high pitch signal is heard AND the "LINE RDY" light remains "ON".

5.1.8 The system will ask the following questions:

a.

System will ask for login. Type in "contrl" AND push "RTN" key.

Page 3 of 15

ENTERGY IP-1 047 INDIAN POINT STATION Rev. 8 EMERGENCY PLANNING

b.

System will ask for password. Type "unit2" AND push "RTN" key.

c.

The following prompt will appear:

Enter:

[em]

EMERGENCY MENU

[dm]

DRILL MENU

[ex]

EXIT

d.

Enter "em" AND push "RTN" key.

e.

The following prompt will appear:

Enter:

[U2] Con Ed Unit 2

[U3] NYPA Unit 3

[EX] Exit

f.

Enter "u2" AND push "RTN" key.

g.

The following prompt will appear:

WELCOME TO MIDAS ENTER:

[XX]

FUNCTION OR TASK CODE

[XXXX]

FUNCTION AND TASK CODE

[FM]

FUNCTION MENU

[EX]

EXIT

h.

Enter "g" AND push "RTN" key.

i.

The following prompt will appear on the screen:

ENTER:

[ST]

STANDARD TIME OR

[DT]

DAYLIGHT SAVING TIME

j.

Choose either standard OR daylight saving time. Standard time is preferred because meteorological data from MIDAS, the MET Display Panel, and data loggers are reported for standard time.

k.

Enter st OR dt AND push "RTN" key.

1.

The following prompt will appear:

ENTER TIME OF REACTOR SHUTDOWN ON 24 HOUR CLOCK Page 4 of 15

ENTERGY IP-1 047 INDIAN POINT STATION Rev. 8 EMERGENCY PLANNING (HRMN)... PRESS RETURN KEY

m.

Enter the time of the reactor shutdown (HRMN) AND push "RTN" key.

n.

The time of reactor shutdown will then be displayed in the following format:

(YRMODAHRMN)

YR = Year MO = Month DA =DAY HR = Hour MN = Minute

o.

IF the time of shutdown is correct THEN push "RTN" key. To change the time of shutdown enter the correct time AND press "RTN" key.

p.

The following prompt will appear:

ENTER:

[YRMODAHRMN]

TIME RELEASE STARTS

[RETURN]

STARTS AT OR BEFORE CURRENTTIME

q.

Since the release has started press "RTN" key to accept default time.

NOTE:

THIS PROGRAM REQUIRES ENTRY OF VALUES FOR CPM (COUNTS

/MINUTE), MR/HR, CFM (CU.FT./MIN), LBS/HR, ETC. NUMBERS CAN BE ENTERED DIRECTLY OR IN ENGINEERING NOTATION. EXAMPLES OF THE NOTATION TO BE ENTER IS AS FOLLOWS:

1) 1,400,000 = 1.4 x 106 = 1.4E6 FOR THIS EXAMPLE, ENTRY WOULD BE 1.4E6

2)

.0000014 = 1.4 x 106 = 1.4E-6 FOR THIS EXAMPLE, ENTRY WOULD BE 1.4E-6

r.

Select the accident release path AND press "RTN" at the following prompt:

SELECT THE ACCIDENT RELEASE PATH

1.

PLNTVNT R-44

2.

PLNTVNT R-27

3.

PLNTVNT CONTACT

4.

R EJTR R-45 Page 5 of 15

ENTERGY IP-1 047 INDIAN POINT STATION Rev. 8 EMERGENCY PLANNING

5.

T LNST MSL ENTER: [N] (1-5) AND PRESS RETURN KEY OR

[EX] TO EXIT

s.

Select units which will be inputted AND press "RTN" at the following prompt:

SELECT UNITS WHICH WILL BE INPUTTED FROM...

1 =CPM 2 = UCI/SEC 3 = UCI/CC ENTER (1-3) AND PRESS RETURN KEY

t.

Enter CPM, Noble Gas release rate OR effluent activity AND press "RTN".

u.

Enter the required effluent flow rate (CFM, Lbs/hr., GPM) AND press "RTN".

v.

IF Meteorological data is unavailable, THEN the following message is displayed:

TIME OF MET: YRMODAHRMN SOME OR ALL MET DATA ARE BAD FOR RELEASE POINT 1 GROUND RELEASE

w.

Manually enter the wind direction (DIR), wind speed (SPD) and delta temperature (DT) AND press "RTN". Refer to Reference 6.2 for other sources of data and conversions to the correct units. Wind speed must be meters/sec. (MS).

Use the lower or ground delta temperature. The current values will then be displayed. To accept current values press "RTN". To correct current values re-enter values AND press "RTN".

x.

Check that the display continues with radiation monitor AND meteorological data in the format of Addendum 8.1. To restart press "S". To continue press "RTN".

y.

Check that the display continues with radiological data in the format of Addendum 8.1.

Page 6 of 15

ENTERGY IP-1 047 INDIAN POINT STATION Rev. 8 EMERGENCY PLANNING

z.

Enter remaining duration of release (IF unknown, THEN enter the default value 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) AND press "RTN" to obtain dose projections..

Press "RTN" to continue.

aa.

When requested to transfer report to broadcast file enter "no" AND press "RTN".

bb.

Enter "s" to stop dose projection program AND press "RTN".

cc.

Exit MIDAS by entering "zz" and press "RTN".

dd.

The telephone line is automatically disconnected.

ee.

Advance paper by pressing "PAPER ADV" key. Detach the printed section by tearing up against the lucite edge.

5.2 Obtaining offsite exposure rates using Windows 95/98 computer terminal.

5.2.1 Computer terminal must have a modem properly connected to access MIDAS.

5.2.2 Click on the Start Buttton MIDAS1ht 5.2.3 From the Programs menu select the Accessories menu and click on the Hyper Terminal icon.

Hyoertrm.exe 5.2.4 IF a MIDAS hyper terminal icon exists THEN double click on it.

5.2.5 To create a MIDAS hyper terminal perform the following:

a.

Double click on the Hypertrm.exe icon.

b.

Type in terminal name (i.e. MIDAS1).

c.

Click on OK

d.

Type in the MIDAS number listed in EPD Book 2 and click on "OK".

5.2.6 Dial MIDAS by clicking on "DIAL".

5.2.7 AFTER the system dials MIDAS, ringing is heard AND a high pitch signal is heard. The modem speaker will then turn off. Press the "RETURN" key to continue.

Page 7 of 15

ENTERGY IP-1 047 INDIAN POINT STATION Rev. 8 EMERGENCY PLANNING 5.2.8 The system will ask the following questions:

a.

System will ask for login. Type in "contrl" AND push "ENTER" key.

Use lower case letters.

b.

System will ask for password. Type "unit2" AND push "ENTER" key.

Use lower case letters.

c.

The following prompt will appear on the screen:

Enter:

[em]

EMERGENCY MENU

[dm]

DRILL MENU

[ex]

EXIT

d.

Enter "em" AND push "ENTER" key.

e.

The following prompt will appear on the screen:

Enter:

[U2] Con Ed Unit 2

[U3] NYPA Unit 3

[EX] Exit

f.

Enter "u2" AND push "ENTER" key.

g.

The following prompt will appear on the screen:

WELCOME TO MIDAS ENTER:

[XX]

FUNCTION OR TASK CODE

[XXXX]

FUNCTION AND TASK CODE

[FM]

FUNCTION MENU

[EX]

EXIT

h.

Enter "g" AND push "RTN" key.

I.

The following prompt will appear on the screen:

ENTER:

[ST]

STANDARD TIME OR

[DT]

DAYLIGHT SAVING TIME

j.

Choose either standard OR daylight saving time. Standard time is preferred because meteorological data from MIDAS, the MET Display Panel, and data loggers are reported for standard time.

Page 8 of 15

ENTERGY IP-1 047 INDIAN POINT STATION Rev. 8 EMERGENCY PLANNING

k.

Enter st OR dt AND push "RTN" key.

I.

The following prompt will appear:

ENTER TIME OF REACTOR SHUTDOWN ON 24 HOUR CLOCK (HRMN)... PRESS RETURN KEY

m.

Enter the time of the reactor shutdown (HRMN) AND push "RTN" key.

n.

The time of reactor shutdown will then be displayed in the following format:

(YRMODAHRMN)

YR = Year MO = Month DA = DAY HR = Hour MN = Minute

o.

IF the time of shutdown is correct THEN push "RTN" key. To change the time of shutdown enter the correct time AND press "RTN" key.

p.

The following prompt will appear:

ENTER:

[YRMODAHRMN]

TIME RELEASE STARTS

[RETURN]

STARTS AT OR BEFORE CURRENT TIME

q.

Since the release has started press "RTN" key to accept default time.

NOTE:

THIS PROGRAM REQUIRES ENTRY OF VALUES FOR CPM (COUNTS

/MINUTE), MR/HR, CFM (CU.FT./MIN), LBS/HR, ETC. NUMBERS CAN BE ENTERED DIRECTLY OR IN ENGINEERING NOTATION. EXAMPLES OF THE NOTATION TO BE ENTER IS AS FOLLOWS:

1) 1,400,000 = 1.4 x 106 = 1.4E6 FOR THIS EXAMPLE, ENTRY WOULD BE 1.4E6

2)

.0000014 = 1.4 x 10- = 1.4E-6 FOR THIS EXAMPLE, ENTRY WOULD BE 1.4E-6

r.

Select the accident release path AND press "RTN" at the following prompt:

SELECT THE ACCIDENT RELEASE PATH Page 9 of 15

ENTERGY IP-1 047 INDIAN POINT STATION Rev. 8 EMERGENCY PLANNING

1.

PLNTVNT R-44

2.

PLNTVNT R-27

3.

PLNTVNT CONTACT

4.

R EJTR R-45

5.

T LNST MSL ENTER: [N] (1-5) AND PRESS RETURN KEY OR

[EX] TO EXIT

s.

Select units which will be inputted AND press "RTN" at the following prompt:

SELECT UNITS WHICH WILL BE INPUTTED FROM...

1 =CPM 2 = UCI/SEC 3 = UCI/CC ENTER (1-3) AND PRESS RETURN KEY

t.

Enter CPM, Noble Gas release rate OR effluent activity AND press "RTN".

u.

Enter the required effluent flow rate (CFM, Lbs/hr., GPM) AND press "RTN".

v.

IF Meteorological data is unavailable, THEN the following message is displayed:

TIME OF MET: YRMODAHRMN SOME OR ALL MET DATA ARE BAD FOR RELEASE POINT 1 GROUND RELEASE

w.

Manually enter the wind direction (DIR), wind speed (SPD) and delta temperature (DT) AND press "RTN". Refer to Reference 6.2 for other sources of data and conversions to the correct units. Wind speed must be meters/sec. (MS).

Use the lower or ground delta temperature. The current values will then be displayed. To accept current values press "RTN". To correct current values re-enter values AND press "RTN".

x.

Check that the display continues with radiation monitor AND meteorological data in the format of Addendum 8.1. To restart press "S". To continue press "RTN".

Page 10 of 15

ENTERGY IP-1 047 INDIAN POINT STATION Rev. 8 EMERGENCY PLANNING

y.

Check that the display continues with radiological data in the format of Addendum 8.1.

z.

Enter remaining duration of release (IF unknown, THEN enter the default value 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />) AND press "RTN" to obtain dose projections..

Press "RTN" to continue.

aa.

To obtain a printout of data perform the following:

1)

Set the Font to 8 using the Font option in the View pull down menu at the top of the screen

2)

Use the scroll bar on the right of the screen to display the data on the screen.

3)

Use click and drag technique with your mouse to highlight the data.

4)

Use the print option in the File pull down menu at the top of the screen to print the highlighted data.

bb.

When requested to transfer report to broadcast file enter "no" AND press "RTN".

cc.

Enter "s" to stop dose projection program AND press "RTN".

dd.

Exit MIDAS by entering "zz" and press "RTN".

ee.

To disconnect click on the disconnect button on the tool bar at the top of the screen.

ff.

To reconnect click on the connect button on the tool bar at the top of the screen.

6.0 6.1 6.2 7.0 REFERENCE IP-1007, "Dose Assessment" IP-1016, "Obtaining Meteorological Data" ATTACHMENTS NONE Page 11 of 15

ENTERGY IP-1 047 INDIAN POINT STATION Rev. 8 EMERGENCY PLANNING 8.0 ADDENDUM 8.1 Summary of Meteorological and Release and Radiological Data 8.2 Calculated Offsite Dose Projections Page 12 of 15

ENTERGY INDIAN POINT STATION EMERGENCY PLANNING ADDENDUM 8.1 Page 1 of 2

SUMMARY

OF METEOROLOGICAL AND RELEASE AND RADIOLOGICAL DATA METEOROLOGICAL DATA PROCESSING IN PROGRESS

• • -CALCULATIONS IN PROGRESS***

SUMMARY

OF METEOROLOGICAL DATA TIME OF MET: 9903231414 GROUND SPEED - METERS/SEC 1.30 M GROUND DIRECTION - DEGREES (FROM) 145. M TEN MILE MAP OVERLAY IDENTIFICATION COLOR YELLOW PASQUILL STABILITY CATEGORY BASED ON DELTA T LETTER D

D

SUMMARY

OF RELEASE DATA ***

TIME OF REACTOR SHUTDOWN 9903231414 RELEASE DATA PLNTVNT N/A R-27 (UCI/SEC) 3.20E-05 ENTER RETURN TO ERASE AND CONTINUE, S TO RESTART,EX TO EXIT 13 of 15 IP-1047 Rev. 8

ENTERGY INDIAN POINT STATION EMERGENCY PLANNING ADDENDUM 8.1 Page 2 of 2

SUMMARY

OF METEOROLOGICAL AND RELEASE AND RADIOLOGICAL DATA

SUMMARY

OF RADIOLOGICAL DATA***

ISOTOPE RELEASE RATE CI/SEC NOBLE GAS RADIOIODINE 3.20E-12 3.20E-16 NORMALIZED DILUTION FRACTION (XU/Q)

SITE BOUNDARY (1432. MTRS) 2 MILES (3218 MTRS) 6.2E-05 1.9E-05 CONCENTRATION (UCI/CC) 5 MILES (8046 MTRS) 5.1 E-06 10 MILES (16093 MTRS) 2.1 E-06 NOBLE GAS RADIOIODINE SITE BOUNDARY 1.5E-16 1.5E-20 OFFSITE DOSE RATE (MREM/HR)

SITE 2

5 BOUNDARY MILES TEDE 7.2E-11 2.2E-11 TODE 8.4E-11 2.6E-11 TIME AFTER SHUTDOWN(HOURS)

TEDE DOSE FACTORS SITE 2

5 BOUNDARY MILES 4.7E+05 4.7E+05 2

MILES 4.8E-17 4.8E-21 10 MILES 3.5E-12 4.5E-12 TRAVEL TIME(HOURS).31

.69 1.72 ENTER REMAINING DURATION OF RELEASE(HRS) FOR DOSE PROJECTIONS RETURN TO STOP 14 of 15 IP-1047 Rev. 8 5

MILES 1.3E-17 1.3E-21 10 MILES 5.1E-18 5.1 E-22 MILES 1.2E-12 1.6E-12

.00 10 MILES 2.8E+05 MILES 2.3E+05 3.44

ENTERGY INDIAN POINT STATION EMERGENCY PLANNING ADDENDUM 8.2 Page 1 of 1 CALCULATED OFFSITE DOSE PROJECTIONS

• • • DOSE PROJECTIONS DOSE PROJECTIONS

• PROJECTION TIME PERIOD (HRS FROM NOW)

(NOW=9903231435)

CLOCK TIME (ST)

TIME

.4 1.4 3.4 7.4 1500 1600 1800 2200 (ST)

SITE BDRY TEDE (REM)

TODE (REM) 2 MILES TEDE (REM)

TODE (REM) 5 MILES TEDE (REM)

TODE (REM) 10 MILES TEDE (REM)

TODE (REM) 0.OE+00 0.OE+00 3.8E-14 1.OE-13 0.OE+00 0.OE+00 4.4E-14 1.2E-13 0.OE+00 0.OE+00 3.3E-15 3.2E-14 0.OE+00 0.OE+00 3.8E-15 3.7E-14 0.OE+00 0.OE+00 0.OE+00 5.OE-15 0.OE+00 0.OE+00 0.OE+00 6.4E-15 0.OE+00 0.OE+00 0.OE+00 1.6E-15 0.OE+00 0.OE+00 0.OE+00 2.2E-15 DAHRMN DAHRMN 231728/

(HOURS) 231853 231751/

231916 231853/

232018 232036/

232201 NOT REACHED NOT REACHED NR)

NR)

NOT REACHED NOT REACHED (NR)

(NR)

NOT REACHED NOT REACHED (NR)

(NR)

NOT REACHED NOT REACHED (NR)

(NR)

• PAG - TEDE = 1 REM, TODE =5 REM

• PAG -TEDE= 1 REM, TODE=5 REM 15 of 15 IP-1047 Rev. 8 PLUME ARVL/

LEAVE TIME (ST)

FROM NOW TO REACH PAG*